Abstract
This work deals with the extraction behavior of neptunium in a high acid Purex Process. The composition of PWR fuel type with 3.2% enrichment, 500 MWd/t burn-up and 100 d cooling time was considered. Two consecutive cold runs were performed in a mock-up facility at IPEN-CNEN/SP with simulated feed solutions containing: 3M HNO3; 1M U; 455 μg237Np labeled with239Np; 15 mg Zr l−1, 12 mg Ce l−1, 7 mg Ru l−1 and 13 mg Mo l−1 traced with active isotopes95Zr,141Ce,103Ru and99Mo as FP. A 30 vol% TBP/n-dodecane was used as solvent. Countercurrent experiments were carried out using two 16 stages plexiglass mixer-settlers, at 25°C, during 21 h continuous operation, with O/A ratio of 2 in the extraction section and 9 and 13 in the 1st and 2nd scrubbing sections, respectively. For a 65% organic loading, ca. 77% of neptunium remains in the waste stream, without any Np valence adjustment.
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de Araujo, B.F., Matsuda, H.T. & Araujo, J.A. Neptunium distribution in a high acid first cycle Purex Process. Journal of Radioanalytical and Nuclear Chemistry Letters 187, 159–168 (1994). https://doi.org/10.1007/BF02162664
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DOI: https://doi.org/10.1007/BF02162664